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Proposed TS 3/4.1.3.1 Re Group Height - Safety & Regulating Rod Groups & TS 3/4.1.3.3 Re Position Indicator Channels
	ML20096C232
Person / Time
Site:	Davis Besse
Issue date:	04/30/1992
From:	; CENTERIOR ENERGY
To:	;
Shared Package
ML20096C205	List: ML20096C200; ML20096C217; ML20096C232;
References
	2028, NUDOCS 9205130233
	Download: ML20096C232 (12)
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Pocket Number 50-346 License Number NPF-3

, Serial. Number 2028 Attachment Page 7 REACTIVITY E CONTROL SYSTEMS 3/4.1.3 MOVABLE CONTROL ASSEMBLIES GROUP HEIGHT - SAFETY AND REGULATING R00 GROUPS 1

LIMITING CONDITION FOR OPERATIONS 3.1.3.1 All control (safety and regulating) rods shall be OPERABLE and positioned within + 6.5X (indicated position) of their group average height.

APPLICABILITY: MODES l' and 2*.

ACTION:

a. With one or more control rods inoperable due to being immovable as a result of excessive friction or mechanical interference or known to be untrippable, tietermine that the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied within one 1.our and be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. With more than one con:rol rod inoperable or misaligned f-om its group average height by more than + 6.55 (indicated position), be in at Ir?st HOT STAN0BY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ,

c. With one control rod inoperable due to causes other than addressed by ACTION a, above, or misaligned fmm its group average heigh ^. by more than + 6.5% (indicated position), POWER OPERATION may continue provided that within one hour either:

1. The control rod is restored to OPERABLE status within

-the above alignment requirements, or

2. The contrcl rod is ' declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 ts satisfied.

POWER OPERATION may then continue provided that:

a) An analysis of the potential ejected rod worth is performed within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and the rod worth is deter-mined to be < l .0". Ak at zero power and < 0.65%

akatRATEDJ AL POW'lR for the remainier of the fuel cycl nd b). The SHUTDOWN MARGIN requirement of Specificatlon

' 3.1.1.1 is determined at least once per 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 3 L

l *5ee special Test Exceptions 3.10.1 and 3.10.2.

! DAVIS-BESSE, UNIT 1 3/4 1-19 9205230233 920430 PDR ADOCd 05000346 P pop

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Doc'ket Number 50-346 License Number NPF-3 Serial Number 2028 Attachment Page 8 l' REACTI ITY CONTROL SYSTEMS l

_ GROUP HEIGHT - SAFETY AND REGULATING ROD GROUPS LIMITING Cf .0! TION FOR OPERATIONS _

ACTIO_N: (Continued) c) A power distribution mp is obtained from the incore dettctorsandFgandFl7 verified to be within their ]

limits wi thin 7. hour ") o ns d, ,

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d) Either the THERMAL POWER level is reduced to < 60% of the THERMAL POWER allowable for the reactor coolant pump combination within one hour and within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months the High Flux Trip Setpoint is reduced to < 70% of the THERMAL POWER allowable for the reactor coolant pump '

combination, or e) The remainder of the rods in the group with the inoperable rod are aligned to within 16.5% of the inoperable rod within one hour while maintaining the position of the rods within the limits provided in the CD'tE OPERATING LIMITS REPORT; the THERMAL POWER level shall be restri:tec pursuant to Specification 3.1.3.6 durirg subsequent

, operation.

SbRVEILLANCE REQUIREMENTS

'l 4.1.3.1.1 The cosition of each control rod shall be determined to be within tne grouo average height limit by verifying the individual rod positions at least once per _12 hours except during time intervals wnen the asymmetric rod monitor is inoperable, then verify the individual rod position (s) of the rod (s). with tne inoperable asymmetric rod monitor at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

4.1.3.1.2 Eact ceatrol rod not fully inserted shall be determined to be OPERAELE by movenient of at least 2% in any one direction at least once eve" 31 days.

DAVIS-BESSE, UNIT 1 3/4 1-20 Amendment ho.135,MA',162

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Mocust Whree ReTC%e License Nutnber NPF-3 'l Serial Nimber 2028

. . %tt'achment Page,9.

a KACTI'.!Ti CONTROL SYSTEMS 00 SIT 10N INDICATOR CHANNELS ;

1' LIMITING CONDITION FOR OPERATION ,

3.1.3.3 ' All safety, regulating -and axial power shaping control rod absolute position indicator enannels and relative position indicator channels shall be OPERABLE and capable of detennining the control--rod group average positions within : 1.5%.

APPLICABILITY: MODES 1 and 2.

ACTION:

a. With a maximum of c::e absolute pos,ition indicator channel oer control rod group or one relative position indicator channel per control red group inoperable either:

1. Reduce THERMAL POWER to < 60% of the THERMAL POWER allcw-able for the reactor cooTant pump combination end reduce the High FluiTrip Setpoint to < 70% of the THERMAL POWER allowable for the reactor coolait pump combination within 8__baur& ~N STAeJur ,, a Pow n~otBurnady. )

2. fprotit.ryma ed: /

'a) The position of the control rod with the inoperable t

position ir.dicator is verified within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months oy l m actuating its 01, 25%, 50", 75% or,- 100 position 3 , .

_ reference indicator, and 3=.

7 g b) < The ' control rod group (s) containing the1 inoperable position indicator channel is subsequently maintained

%vo at tha 0%, 25%, 50%, 75% or.E100% withdrawn . position

'T t,N verified at this position at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter, and

-37 qU Operation is within the limits of SOcificationj 3.3.3 5 c) ~~~~

3.1.3.6for 3. n , L9, M bffb4Ie;.

I' IMh .a +han one relgtive position indicator rasie!

L operation in M00n i and 2 -menat. r up to 24 tours o osi h e rhannels are i c.;

Tle pyvis,cns cA S p,Jhday ,3,c,4 ,,.e.

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DAVIS-BESSE, UNIT 1- 3/4=1-22 ;cenament Sc.152 l

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Docket Number 50-346: !

License Number NPF-3 '!

-. Serial ~ Number 2028:- ;l

-Attachment ,

JPage:10~-

-a New 3.1.3.3 Action

b. Vith more than one relative position' indicator enannel per. control rod

-group inoperable, STARTUP and POVER OPERATION may continue provided~that the requirements of-either Action a.1 or a.2 above have been complied with and:the-' absolute position indicator channels are OPERABLE for the affected

. control--rod tasemblies.

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Docket Number 50-346 License Numb 3r NPF-3 Serial Number 2028 Attachment

Page 11

!:REA'CTI'llTY CONTROL SYSTEMS ii IN:CN'ON ONJ l 'P051T:0N INDICA'OR CHANNEL 5_ (Continueci SURVEILLANC(3E0VIREMENTS

,}4.1.3.3 Enct. absolute and relative positiv. 4dicator channel shall be i

determined to u. OPERABLE by verifying that the i 31ative position indicator channels and the absolute position indicator channels agree within 3.46% at least ance per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time intervals when the asymetric rod monitor is inoperable, then comoare the relative position indicator and absolute position indicator cnannel(s) of the rod (s) with the inoperable asymetric rod monitor at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

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l OMIS-BESSE, UNIT 1 3/4 1-23 Amendment No.162

~ ' Docket' Number.50-346 ,

License Number NPF-3 i Serial' Number 2028 1

, . Attachment Page 12 REACTIVITY CONTROL' SYSTEMS NF01MA7N ON Y SAFETY ROD IM5ERTION LIMIT LIMITING CONDITION FOR OPERATION 3.1. 3. 5 All safety rods shall be fully withdrawn.

APPLICABILITY: 1* and 2*#.

ApTION:

With a maximum of one safety rod not fully withdrawn, except for sur-veillance testing pursuant tn Specification 4.1.3.1.2, within one hour either:

a. Fully withdraw the rod or

b. Declara the rod te be inoperable and apply Specification 3.1.3.1.

SURVEILLANCE REQUIREMENTS 4.1. 3. 5 Each safety rod shall be determined to be fully withdrawn:

a. Within 15 minutes prior to withdrawal of any regulsiing rod during an approach to reactor criticality.

b. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

See Special Test Exception 3.10.1 and 3.10.2.

fWith K,ff a 1.0.

DAVIS-BESSE, UNIT 1 3/4 1-25 J

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Docket'NumbeY S)-}546 License Number NPF-3 Serial Number 2028 Attachment Page 13 REACTIVITY CONTRCL SYSTEMS khhN I}kj REGULATING ROD INSERTION LIMITS LIF'! TING CONDITION FOR OPERATION 3.1. 3. 6 The regulating rod groups sna11 be positioned within the acceptable operating limits for regulating roc position prcvided in the CORE OPERATING LIM 112 .1EPORT. !

, 2 APPLICABILITY: MODES 1* and 2*f.

ACTION:

Wiut the regulating rod groups inserted beyond the operating limits (in a region other than acceptable operation), or with any group sequence or overlap l

outside the limits provided in the CORE OPERATING LIMITS REPORT except for surveillance testing pursuant to Specification 4.1.3.1.2 either:

a. Restore the regulating groups to within the limits provided in the CORE OPERATING LIMITS REPORT within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , or !

b. Reduce THERMAL POWER to less than or equal to that fraction of RATED THERMAL POWER which is allowed by the rou group position limits provided in the CORE OPERATING LIMITS REPORT within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or

c. Be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

NOTE: If in unacceptable region, also see Section 3/4.1.1.1.

See Special Test Exception 3.10.1 and 3.10.2.

With Xeff > 1.0.

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1 DAVIS-BESSE, UNIT 1 3/4 1-25 Amendment No. JJ,33,AJ A2 /3.51c E7 E0.723, 144

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DoUket Ndmber 50-346' 1.icense Number NPF-3 Serial Number 2028

, Attachment id[CTY/ITYCONTROLSYSTEMS REGULATING R00 INSERTION LIMITS [QQM{}Qg ((y

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SURVEILLANCE REQUIREMENTS 4.1.3.6 The position of eacn regulating group shall be determined to be wit'ain the limits provided in the CORE OPERATING LIMITS REPORT at least once j every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except when:

a. The regulating rod insertion limit alarm is inoperable, then verify the groups to be within the insertion limits at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; 1

' b. The contN. rod drive sequence alam is inoperable, then verify the groups to be within the sequence and overlap limits at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

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, ' ,1 w DAVIS-BESSE, UNIT 1 3/4 1-27 Amenament No.144 (next page is 3/41-30) l

License Number NPF-3 Serial Number 2028

- Attachment Page 15 REACTIVITY CONTROL SYSTEMS

'XIAL POWER SifAPING R00 INSERTION LIMITS LIMITING CONDITION FOR OPERATION _

3.1.3.9 The axial power shaping rod group shall be w: thin the acceptable operating limits for axial power shaping rod position specified in the CORE OPERATING LIMITS REPORT.

APPLICABILITY: MODES 1 and 2*.

ACTION:

With the axial power shaping rod group outside the above insertion limits, either:

a. Restore the axial power shaping rod group to within the limits within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , or

b. Reduce THERMAL POWER to less than or equal to that fraction of RATED THERMAL POWER which is allowed by the rod group position using the acceptable operating limits provided in the CORE OPERATING LIMITS REPORT within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , or

e. Be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS , 4.1.3.9 The position of the axial power shaping rod group chall be detennined to ba within the limits provided in the CORE OPERATING LIMITS REPORT at least once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except when the axial power shaping rod insertion limit alam is inoperable, then verify the group to be within the limit orovided in the CORE OPERATING LIMITS REPORT at least once every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

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With k eff 1 1.0.

DAVIS-BESSE, UNIT 1 3/4 1-34 Amendment No. 33 f 2,15,6J ,E9, 30*I23'l44 (Next ~ s,is 3/4 2-1)

Docket Number 50-346

! License Number NFP-3

! - .- Serial Number 2028 Attachment Page 16

. KEAdnu i CONTROL SYSTEMS S P W M- @ .y l

BA5ts 3/4.1.2 B0 RATION SYSTIMS (Continued) stable reactivity condition of the reactor and the additiocal restrictions prohibiting C0KE ALTERATIONS and positive reactivity change in the event the single injection systen becomes inoperable.

The boren capability required belov 200'F is sofficient to provide a SHUTDOVN MARGIN of 1% ak/k af ter senen decay and cooldovn f ate 200'F to 70'F. This condition ret;uires 'either 600 gallons of 7875 ppa borated water from the boric acid storage cystem or 3,000 gallons of 1800 ppe -

berated water from the borated vater stcrete tank.

The batta 4 inches of the borated vater storage tank ars not available, and the instrumentation is :slibrated to reflect the available volume.

All ber4 e acid tank volume is available. The limits on water volume, and boren concentrntion ensure a pH value of betvesa 7.0 and 11.0 of the solution recirculated within containnnt atter a design basis accident, e The pH band minimises the svolution of iodine and minimises the effect of chleride and caustic stress corrosion cracking ou mechanical systems

- and compontnts.

The OPERABILITY of one boron injection systen during RETUILING ansures that this system is available for reactivity control while in MODE 6.

3/4.1.3 H0VABLE CON"1 tot ASSEMBLIES The specifications of this section (1) ensure that acceptable power distribution limits ara maintained (2) ensure that the minista SHUTD0VN MARGIN is maintained, and (3) limit the potamial effects of a rod -

ejection accidsnt. OPERASILITT of thq control rod position indicators is required to determine control red positions and*thereby ensure compliance with the ccatrol rod alignment and insertion limits.

+ The ACTION statements which permit limited variations free the basic requirasents are accespanied by additional restrictions which ensure that he original criteria are eat. Fer example, aisalignment of a safety or regulating rod requires a restriction in TIIRMAL POTER. The reactivity vorta et a assaligned red is limited for the reasinder of the fuel cycle to prevent exceeding the assumptions used in the safety a.salysis.

The position of a rod declared inoperable due to aisalignment should net be included in computing the average group position for determining the CFERABILITY of rods with lesser aisalignments.

l P/ES-BESSE, UNIT 1 2 3/4 1-3 Amandacnt No. 123 1

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DocketNumberiddU License Number NPF-3

, Serial Number 2028 Attachment Page 17 REACTIVITY CONTROL SYSTEMS [h hj BASES _ _

3/a.1. 3. MOVABLE CONTROL ASSEMBLIES (Continued)

The maximum rod drop time pemitted is consistent with the assumed rod drop time used in the safety analyses. Measurement with T > 525'F and with reactorcoolantpumpsoperatingensuresthatthemeas0Nddroptimeswillbe representative of insertion times expenenced during a reactor trip at operating conditions.

Control rod positions end GPERABILITY of the rod position indicators are required to be verified on a naminal basis of once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months with frequent verifications required if an automatic monitoring channel is inoperable.

These verification frequencies are adequate for assering that the applicable LCO's are satisfhd. A 1.5% group avcrage position uncertainty is applied to i the rod index curves. Therefore, the position indicators must be capable of I supporting this accuracy. The Surveillance Requirement ensures this accuracy I by keeping the RPI calibrated to a "known" position as indicated by the API.

Using the API as a "known" position is valid provided two consecutive reed switches are not inoperable. Having one entire string (i.e., every other reed switch) inoperable is acceptable.

A specific surveillance of the reed switches is not required because:

l 1) When one or rncre reed switch fails closed, a large API indication of j asymmetry occurs.

Il 2) Two failed open reed switches in series result in a large indication

{ of asymetry.

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3) Failed open reed switches not in series (up to every other switch) are bounded by the analysis.

Therefore, a reed switch condition not bounded by the analysis will be indicated by API system asymetry indications.

Technical Specification 3.1.3.8 provides the ability to prevent excessue pow" peaking by transient xenon at RATED THERMAL POWER. Operating restric-tions: resulting from transient xenon power peaking, including xenon-free startup, are inherently included in the limits of Sections 3.1.3 Rod Insere'on Limits). 2,.1.3.9 (Axial Power Shaping Rod Insertion Limits), and 3.2.1 (Axial Power Imbalance) for transient peaking behavior bounded by the following factors. Fct the period of cycle operation where regulating rod groups 6 and 7 are ellowed to be inserted at RATED THERMAL POWER, an 8% peaking increase is applied at or above 92% FP. An 18% increase is applied oclow 92*.

FP. For operation where only regulating rod group 7 is allowed to be inserted at RATED THERWd. POWER, a 5% peaking increase is applied at or abeve 92% FP and a 135 increase is applied below 92% FP.

DAVIS-BEsSE,UNIl1 B 3/4 1-4 Amencment No. 4 . 162 l

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Docket Number 50-346 License Number NPF-3 Serial Number 2026

-Attachment P.sge 18

!N E W M tm y

, f *CT:',ITY CCNTROL SYSTEMS

-} ' , 54SE5 --

i p/4.1.3 uGVABLE CONTA0L ASSEMBLIE5 (reatinued)

} lIf these values, checked avery cycle, conservatively bound the peaking effects j tof all transient xenon, then the need for any hold at a power level cutoff 1 jbelow etATED THERMAL POWER is precluded.

If not, either the power level at

'wnicn the requirements of Section 3.1.3.8 must be satisfied or the above-listed f act:rs will be suitably adjusted to creserve the LOCA linear heat rate limits.

llThe

' that ::wer lit.itation on axial peaking cower limits shacing are not exceeded. red insertion is necessary to enstre

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I DAVIS-BESSE, UNIT 1 B 3/4 1-d Amer.dment No. 33, 4 152 !

ML20096C232

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